Prediction of axial DNBR distribution in a hot fuel rod using support vector regression models

IEEE Transactions on Nuclear Science

Volumn 58, Issue 4 PART 2, 2011, Pages 2084-2090

  Kim, Dong Su ^a   Lee, Sim Won ^a   Na, Man Gyun ^a  

^a Chosun University   (South Korea)

Author keywords

Critical heat flux; data based method; departure from nucleate boiling ratio (DNBR); hot fuel rod; support vector regression (SVR)

Indexed keywords

AXIAL LOCATIONS; CRITICAL PARAMETER; DATA-BASED METHOD; DEPARTURE FROM NUCLEATE BOILING; DEPARTURE FROM NUCLEATE BOILING RATIOS; FUEL CYCLE; FUEL RODS; HOT FUEL ROD; LEARNING DATA; MEASURED SIGNALS; MONITORING INFORMATION; OPERATING MARGINS; PROTECTION SYSTEMS; REACTOR COOLANT SYSTEMS; ROOT-MEAN-SQUARE ERRORS; SAFETY ISSUES; SUPPORT VECTOR REGRESSION (SVR); SUPPORT VECTOR REGRESSION MODELS; SUPPORT VECTOR REGRESSIONS; TEST DATA; TIME STEP;

HEAT FLUX; NUCLEAR POWER PLANTS; NUCLEAR PROPULSION; NUCLEAR REACTORS; NUCLEATE BOILING; PHASE TRANSITIONS; REGRESSION ANALYSIS; STATISTICAL TESTS;

FUELS;

EID: 84860411431     PISSN: 00189499     EISSN: None     Source Type: Journal    
DOI: 10.1109/TNS.2011.2159738     Document Type: Article

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